Benchmark Specifications for TREAT Tests M5, M6, and M7
- Argonne National Laboratory (ANL), Argonne, IL (United States)
Detailed information describing three TREAT tests performed on metallic fuels has been collected and organized for use as a benchmark in evaluating the performance of metallic fuel models and codes. The tests, designated M5, M6, and M7, subjected EBR-II-irradiated fuel pins to a single type of overpower transient (at prototypical conditions with full coolant flow and an exponential power rise on an 8 second period) in flowing sodium loops. Six fuel pins were tested; five were ternary (U-19Pu-10Zr) alloy fuel clad in D9 with burnup ranging from 0.8 to 9.8 at. %, and one was binary alloy fuel (U-10Zr) clad in HT9 with 2.9 at. % burnup. The information gathered from the test records is expected to be useful for pre-transient characterization of the irradiated fuel pins as well as the transient analysis of the metallic fuel when subjected to severe accident conditions. This report presents benchmark specifications for the M5, M6, and M7 TREAT tests, identifies where primary sources of benchmark-related information can be found, and includes background information to help a user of the data understand their applicability and limitations.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE), Office of Advanced Reactor Technologies
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1924431
- Report Number(s):
- ANL-ART-174-Rev.1; 181061
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel motion in TREAT tests M5F1, M5F2, M6 and M7: preliminary analysis of hodoscope data
Transient feedback from fuel motion in metal IFR (Integral Fast Reactor) fuel
First TREAT transient overpower tests on U-Pu-Zr fuel: M5 and M6
Technical Report
·
Sat Jul 01 00:00:00 EDT 1989
·
OSTI ID:714612
Transient feedback from fuel motion in metal IFR (Integral Fast Reactor) fuel
Conference
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:6817951
First TREAT transient overpower tests on U-Pu-Zr fuel: M5 and M6
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6941607